A comprehensive study on the phase composition, mechanical properties and stability of Li4SiO4-Li2ZrO3 biphasic ceramics

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-07-20 DOI:10.1016/j.jnucmat.2024.155300
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Abstract

Lithium orthosilicate (Li4SiO4) is regarded as a candidate for tritium breeding in fusion reactors. In this study, the Li4SiO4-Li2ZrO3 biphasic was developed to improve the sinterability, density, and mechanical properties of Li4SiO4. The Li4SiO4-xLi2ZrO3 (x = 0.5, 1) composite powders were prepared using solid-state reaction via in-situ method. Li6Zr2O7 existed in the ceramic powders at low calcination temperatures. When the calcination temperature was increased to 900 °C, Li6Zr2O7 was transformed into Li2ZrO3 due to the decomposition of Li6Zr2O7 at high temperatures. The TEM observation confirmed that the powders consisted of Li4SiO4 and Li2ZrO3. The Li4SiO4 and Li4SiO4-xLi2ZrO3 (x = 0.5, 1) pebbles were fabricated by the sol-gel method. The measurement results showed that the pebbles had a narrow size distribution and fine sphericity. The density of Li4SiO4-Li2ZrO3 pebbles reached 96.01% of the theoretical density when it was sintered at 1000 °C for 4 h. Compared with the Li4SiO4, the grain size of ceramic pebbles was significantly reduced. Owing to decreased grain size, 139.0 N crush load for the pebbles and 92.4 MPa bending strength for the sintered bodies were achieved. Besides, the ceramics with the Li4SiO4 to Li2ZrO3 ratio of 2: 1 exhibited preferable mechanical properties. Further, to investigate the chemical stability of biphasic ceramics, the structure and mechanical properties were examined under high temperatures and continuous inert gas purging, simulating the working condition of fusion reactors. It was shown that there was almost no change in phase composition and grain size after purging for 60 h at 650 °C. For the mechanical properties, the crush load was decreased initially due to the cracking in the surface region of the ceramic and then increased because the cracking was recovered.

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关于 Li4SiO4-Li2ZrO3 双相陶瓷的相组成、力学性能和稳定性的综合研究
正硅酸锂(LiSiO)被认为是聚变反应堆中氚培育的候选材料。本研究开发了 LiSiO-LiZrO 双相材料,以改善 LiSiO 的烧结性、密度和机械性能。通过原位法利用固态反应制备了 LiSiO-LiZrO ( = 0.5, 1) 复合粉末。在低煅烧温度下,陶瓷粉末中存在 LiZrO。当煅烧温度升至 900 ℃ 时,由于 LiZrO 在高温下分解,LiZrO 转变为 LiZrO。TEM 观察证实粉末由 LiSiO 和 LiZrO 组成。通过溶胶-凝胶法制备了 LiSiO 和 LiSiO-LiZrO ( = 0.5, 1) 卵石。测量结果表明,鹅卵石的粒度分布较窄,球形度较好。在 1000 °C 下烧结 4 小时后,LiSiO-LiZrO 卵石的密度达到理论密度的 96.01%。由于晶粒尺寸减小,鹅卵石的压碎载荷达到了 139.0 N,烧结体的抗弯强度达到了 92.4 MPa。此外,LiSiO 与 LiZrO 之比为 2:1 的陶瓷具有更好的机械性能。此外,为了研究双相陶瓷的化学稳定性,还在高温和连续惰性气体吹扫条件下(模拟核聚变反应堆的工作条件)对其结构和机械性能进行了检测。结果表明,在 650 °C 下吹扫 60 小时后,相组成和晶粒大小几乎没有变化。在机械性能方面,由于陶瓷表面区域出现裂纹,压碎载荷最初有所降低,随后由于裂纹得到恢复,压碎载荷有所升高。
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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